Guangchao Yang , Xiaojing Liu , Decao Wu , Jinbiao Xiong , Tengfei Zhang , Xiang Chai , Hui He
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引用次数: 0
Abstract
The thickness of Corrosion-Related Unidentified Deposits (CRUD) on the surface of Pressurized Water Reactor (PWR) fuel cladding is one of the key factors affecting fuel performance. Accurate measurement of CRUD thickness is crucial for ensuring the safe operation of nuclear reactors. This paper presents an online, in-situ, non-contact CRUD thickness measurement method based on the photoacoustic effect, overcoming the issues of surface morphology changes and re-dissolution associated with traditional offline measurement methods. To validate the feasibility and accuracy of this method, an experimental system was established, and the signal transmission mechanisms involved in the thermal-fluid–solid multi-physics fields of the measurement method were explored using a simplified 1D mathematical model and 3D simulations. The results show that the method enables low-cost, high-precision measurements, requiring only a 532 nm wavelength, 700 Hz modulation frequency, and 3 W full power Pulse Width Modulation (PWM) pulsed laser as the signal excitation source, along with a piezoelectric transducer as the signal receiver. The simplified 1D mathematical model and 3D simulation results align well with experimental data, with a maximum error of ±10 %. The results show that under the same laser operating conditions, the CRUD thickness is approximately proportional to the output signal intensity with a good linear relationship. This measurement method and its mathematical model provide significant technical and theoretical support for studying the dynamic growth behavior of CRUD.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.